studymcnpandgeant

1D-Monte-Carlo

This is an assignment for Adv Reactor Physics, which creates a 1D Monte Carlo simulation.

1D_Diffusion

A 1-dimensional diffusion neutron transport solver.

22.211-Course-Project

Monte Carlo code for solutions to my problem sets for MIT's 2012 22.211 course

3D_SN_KBA

3D_SN_KBA_OPT

benchmark

compare serpent and mcnp full core result

ClassifiedMC_FET

CMFD

CombLayer

MCNP(X) project builder using C++

csg2csg

Tools to translate between different CSG geometry types

studymcnpandgeant/1D-Monte-Carlo

This is an assignment for Adv Reactor Physics, which creates a 1D Monte Carlo simulation.

studymcnpandgeant/1D_Diffusion

A 1-dimensional diffusion neutron transport solver.

studymcnpandgeant/CombLayer

MCNP(X) project builder using C++

studymcnpandgeant/csg2csg

Tools to translate between different CSG geometry types

studymcnpandgeant/daima

studymcnpandgeant/Deterministic_Transport

studymcnpandgeant/detran-examples

Examples (and benchmarks) for libdetran

studymcnpandgeant/dissertation

Advanced Quadrature Selection for Monte Carlo Variance Reduction

studymcnpandgeant/fermi

Nuclear Reactor Code

studymcnpandgeant/libdetran

deterministic transport utilities

studymcnpandgeant/mcpl

Monte Carlo Particle Lists

studymcnpandgeant/MonteCarlo_Cpp

Monte Carlo neutron transport solver written in C++.

studymcnpandgeant/narrows

Narrows solves the discrete ordinates transport equation using a neural network.

studymcnpandgeant/neutral

A Monte Carlo Neutron Transport Mini-App

studymcnpandgeant/neutron_validation

Repository containing files pertinent to the simulation of specific neutron transport benchmarks.

studymcnpandgeant/nuclear-1

Self-written montecarlo code and its application to track neutron moderated in nuclear reactor + comparison of 3 materials number of collision needed to moderate neutron.

studymcnpandgeant/NuclearSims

Nuclear Reaction Monte Carlo Simulation Package from WUSTL

studymcnpandgeant/openmc

OpenMC Monte Carlo Code

studymcnpandgeant/OpenMOC

A method of characteristics code for nuclear reactor physics calculations.

studymcnpandgeant/osu-transport

studymcnpandgeant/point_reactor

基于一阶泰勒展开的点堆中子动力学方程求解程序

studymcnpandgeant/pyne

PyNE: The Nuclear Engineering Toolkit

studymcnpandgeant/RMC_TestNucData

studymcnpandgeant/simplemc

This is just a toy MC code to get familiar with Monte Carlo process

studymcnpandgeant/thermalNeutronWork

General work related to thermal neutron scattering and the importance of phonon distribution representations

studymcnpandgeant/USTC-CS-Courses-Resource

**科学技术大学计算机学院课程资源(https://mbinary.xyz/ustc-cs/)

studymcnpandgeant/vpncn.github.io

2021**翻墙软件VPN推荐以及避坑指南，对比SSR机场、蓝灯、WireGuard、V2ray、老王VPN、VPS搭建梯子等科学上网软件与方法，**最新科学上网翻墙VPN梯子下载推荐，稳定好用。

studymcnpandgeant/vpnforchina.github.io

翻墙软件攻略，**VPN推荐指南2020版 - 国内还能用的翻墙VPN就这几个了。科学上网、翻墙工具vpn推荐最新地址。

studymcnpandgeant/warp

continuous energy monte carlo neutron transport in general geometries on GPUs

studymcnpandgeant/wu_program